2021 Annual Meeting

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[2L01-05] Structural Materials 1 (FeCrAlZr-ODS)

Thu. Mar 18, 2021 9:30 AM - 10:55 AM Room L (Zoom room 12)

Chair: Takuya Nagasaka (NIFS)

10:15 AM - 10:30 AM

[2L04] Application of FeCrAlZr-ODS alloy for advanced liquid blanket and divertor concepts

(4)Experimental study on chemical compatibility for the development of fusion reactor components

*Masatoshi Kondo1, Jyunichi Miyazawa2, Teruya Tanaka2, Naoko Oono3, Masafumi Akiyoshi4, Kan Sakamoto5, Yoshitaka Ueki6, Yuji Hatano7, Bruce Pint8, Jun Jiheon8 (1. Tokyo Tech, 2. NIFS, 3. Hokkaido Univ., 4. OPU, 5. NFD, 6. Osaka Univ., 7. Univ. of Toyama, 8. ORNL)

Keywords:Liquid blanket, Liquid divertor, FeCrAlZr-ODS, Chemical compatibility, Irradiation

Chemical compatibility of liquid metals with structural materials is one of the important issues for the development of liquid breeder blanket and liquid divertor concepts. The chemical compatibility is influenced by the liquid temperature, liquid flow conditions, and the chemical impurities. The effect of irradiation on the chemical compatibility has rarely been investigated so far. Japan and US joint research project “FRONTIER” started in 2019 to investigate the reaction dynamics at interfaces in DEMO divertor systems and irradiation effects. The recent activities such as corrosion tests under electron irradiation and capsule design for HIFR irradiation tests are going to be reported in the presentation.